Symposium on the reprocessing of irradiated fuels. Book 1, Sessions I, II, and III

Technical Report · Fri Oct 31 00:00:00 EST 1958

DOI:https://doi.org/10.2172/4335654· OSTI ID:4335654

Book one of this conference is divided into 3 sessions: Session I: Aqueous Reprocessing (9 papers); Session II: Auxiliary Processes (9 papers); and Session III: Disposal of Plant Effluents (6 papers). In Aqueous Reprocessing, typical chemical processes for dissolving and preparing relatively simple fuel elements (Al clad or canned) for solvent extraction treatment are discussed. Typical chemical and process flowsheets for solvent extraction separation and decontamination of U-- Pu in natural uranium, U/sup 233/--Th from thorium, and enriched uranium from U-Al alloy are presented. Performance characteristics of packed columns in Redox Process, and pulse columns and mixer settlers in Purex Process are given. Auxiliary Processes are those dealing with unusual fuels, converting them to solutions amenable to solvent extraction. The most widely proposed diluents and claddings for these power reactor fuels are Zr and stainless steel, and the various methods for dissolving them are surveyed. Also described as auxiliary processes are methods for additional decontamination from Ru, Zr, and Nb, for concentrating dilute U/sup 233/ and Pu, and for calcining UNH to UO/sub 3/ and converting Pu(NO/sub 3/)/sub 4/ to metal. In Disposal of Plant Effluents the methods used for treatment, concentration, storage, and dispersal of gaseous, liquid, and solid wastes from radiochemical processing plants are summarized. After waste disposal problems are treated in general, the treatment of gaseous effluents, preparation of waste for liquid disposal, and the retention of high level radioactive wastes are discussed. The problems of ultimate disposal of radioactive waste to the environment are surveyed with consideration of the development of a nuclear power economy during the next fifty years. Unit costs and economic relationships for some of the better understood stages of the general scheme of waste disposal arc derived.

• Research Organization: Atomic Energy Commission, Washington, D.C.
• NSA Number: NSA-12-000154
• OSTI ID: 4335654
• Report Number(s): TID-7534 (Book 1)
• Resource Relation: Conference: PAPERS PRESENTED AT THE BELGIUM SYMPOSIUM ON CHEMICAL REPROCESSING, BRUSSELS, MAY 20-24, 1957; Other Information: Orig. Receipt Date: 31-DEC-58; Related Information: Original cited in NSA as 1 record for the 3 books of the conference; in 2006, electronic versions were created for each of the three books, each with full text.
• Country of Publication: United States
• Language: English

Related Subjects

CHEMISTRY
ALUMINUM ALLOYS
BROMINE FLUORIDES
CHEMICAL REACTIONS
CHLORINE FLUORIDES
DECONTAMINATION
ENRICHMENT
EXTRACTION COLUMNS
FLUORIDES
FUELS
ISOTOPES
LABORATORY EQUIPMENT
MELTING
METALLURGY
NIOBIUM
PLUTONIUM
PLUTONIUM NITRATES
PREPARATION
PUREX PROCESS
PYROLYSIS
RADIATIONS
RADIOCHEMISTRY
RECOVERY
REDOX PROCESS
REPROCESSING
RUTHENIUM
SAFETY
SEPARATION PROCESSES
SOLUTIONS
SOLVENT EXTRACTION
STEELS
THORIUM
URANIUM
URANIUM 233
URANIUM TRIOXIDE
VOLATILITY
WASTE DISPOSAL
WASTE PROCESSING
WASTE SOLUTIONS
WATER
ZIRCONIUM